Experimental setup for simulating entrainment in reactor hot leg

Abstract

The invention discloses a test device for simulating the entrainment of the hot leg section of a reactor, comprising: a first pipe, the first end of which is connected to the outlet of the pressure vessel of the reactor; a second pipe; a three-way pipe, the three-way pipe includes The first end, the second end, the third end, the first end of the three-way pipe is connected with the second end of the first pipe, the second end of the three-way pipe is connected with the first end of the second pipe, and the The third end is used to connect with the automatic pressure relief system of the reactor, and the tee pipe is made of polycarbonate; the third pipe, the first end of the third pipe is connected with the second end of the second pipe, and the third pipe is connected with the second end of the second pipe. The first end is connected to the evaporator inlet of the reactor, and the third tube is curved. According to the test device for simulating the entrainment of the reactor hot leg section of the present invention, double-ended air intake can be realized, and it can be used to carry out experimental research on the entrainment of air-water at normal temperature and steam-water at high temperature, and it is convenient for the observation of the experiment. The bent third tube can simulate the real structure of the reactor heat pipe section.

Description

technical field [0001] The invention belongs to the technical field of nuclear experiment devices, and in particular relates to a test device for simulating entrainment in the hot leg section of a reactor. Background technique [0002] The tee structure is widely used in nuclear power plants. Taking AP1000 of the third-generation nuclear power plant as an example, the heat pipe section and the fourth-stage automatic depressurization system (the forth Automatic Depressurization System, ADS-4) pressure relief pipeline have a three-way pipe structure. ADS is an important part of the AP1000 passive safety system. When a small breach accident occurs, the opening of the ADS-4 burst valve can effectively reduce the pressure of the pressure vessel in the later stage of the accident, and realize the In-Containment Refueling Water Storage Tank (In-ContainmentRefuelingWaterStorage Tank, IRWST) internal cooling water is injected into the core under the action of gravity to prevent the ...

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Problems solved by technology

At the same time, after the ADS-4 valve was opened, the core pressure continued to decrease, and with the flashing of a large amount of steam, the coolant charge in the primary circuit continued to decrease, which may lead to serious accidents such as core exposure or even burning. The experimental research of two-phase entrainment is mainly based on single-end intake, but this is not consistent with the actual situation, and cannot accurately simulate the prototype reactor

[0004] In the related technology, the hardness of the tee pipe is high, and it is easy to break when the pipe vibrates, so it can only be used for low flow experiments

And it is impossible to carry out the steam-water entrainment experiment under normal pressure. Therefore, it cannot meet the requirements of the ADS-4 entrainment experiment and the steam-water entrainment experiment under a large flow rate, and it cannot better simulate the real structure of the prototype reactor.

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